CRITICAL EXPERIMENTS WITH FAST TEST REACTOR-FUEL PINS IN WATER

被引：4
|
作者：
BIERMAN, SR [1 ]
DURST, BM [1 ]
CLAYTON, ED [1 ]
SCHERPELZ, RI [1 ]
KERR, HT [1 ]
机构：
[1] OAK RIDGE NATL LAB,OAK RIDGE,TN 37830
来源：
NUCLEAR TECHNOLOGY | 1979年 / 44卷 / 01期
关键词：
D O I：
10.13182/NT79-A32247
中图分类号：
TL [原子能技术]; O571 [原子核物理学];
学科分类号：
0827 ; 082701 ;
摘要：
引用
收藏
页码：141 / 151
页数：11
相关论文
共 50 条
  • [31] ON THE FAILURE OF FAST-REACTOR FUEL-PINS
    MATTHEWS, JR
    PREUSSER, T
    NUCLEAR ENGINEERING AND DESIGN, 1987, 101 (03) : 281 - 303
  • [32] OXYGEN GETTERS FOR FAST-REACTOR FUEL PINS
    JOHNSON, CE
    FEE, DC
    NUCLEAR TECHNOLOGY, 1978, 40 (01) : 89 - 97
  • [33] GENERAL CHARACTERISTICS OF FAST-REACTOR FUEL PINS
    KUMMERER, K
    TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1975, 20 (APR21): : 301 - 304
  • [34] PERFORMANCE OF LIQUID-METAL REACTOR-FUEL PINS WITH D9 CLADDING
    MAKENAS, BJ
    HALES, JW
    TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1985, 50 (NOV): : 242 - 244
  • [35] THE FAST-NEUTRON REACTOR-FUEL ELEMENT AND ITS BEHAVIOR
    LECLERE, J
    MILLET, P
    ANNALES DE CHIMIE-SCIENCE DES MATERIAUX, 1984, 9 (04): : 423 - 431
  • [36] DERIVATION OF CONSISTENT MEASURES FOR DOUBLING OF FAST BREEDER REACTOR-FUEL
    OTT, KO
    BORG, RC
    NUCLEAR SCIENCE AND ENGINEERING, 1977, 62 (02) : 243 - 261
  • [37] LIGHT WATER REACTOR-FUEL ROD PERFORMANCE - OVERVIEW
    ROBERTS, JTA
    AMERICAN CERAMIC SOCIETY BULLETIN, 1976, 55 (04): : 457 - 457
  • [38] HEAT RELEASE FROM REACTOR-FUEL ELEMENTS FOR FAST TRANSIENTS
    WEST, G
    WARME UND STOFFUBERTRAGUNG-THERMO AND FLUID DYNAMICS, 1980, 14 (02): : 75 - 80
  • [39] PHENIX FAST BREEDER REACTOR-FUEL DISMANTLING HOT CELL
    THEVENOT, L
    MOREAU, C
    TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1976, 24 (NOV19): : 505 - 506
  • [40] THERMAL-HYDRAULIC ANALYSIS FOR EXPERIMENTAL DEVICE OF SUPERCRITICAL WATER REACTOR-FUEL QUALIFICATION TEST
    Liu, Liang
    Zhou, Tao
    Li, Yu
    Cheng, Wanxu
    Chen, Juan
    Huang, Shanfang
    Huang, Yanping
    PROCEEDINGS OF THE 22ND INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING - 2014, VOL 5, 2014,
12345